作者: D. P. Abraham , J. W. Richardson Jr. , S. M. McDeavitt
关键词: Microstructure 、 Zirconium alloy 、 Metal 、 Alloy 、 Energy-dispersive X-ray spectroscopy 、 Materials science 、 Zirconium 、 Metallurgy 、 Neutron diffraction 、 Scanning electron microscope
摘要: The electrometallurgical treatment of zirconium-based and Zircaloy-clad spent nuclear fuels will yield a metal waste form. baseline composition for the form is zirconium-8 wt% stainless steel (Zr-8SS). microstructure Zr-8SS alloy has been studied by scanning electron microscopy, energy dispersive spectroscopy, neutron diffraction. phases present in as-cast include Zr(α), Zr3(Fe,Ni), Zr2(Fe,Ni), Zr2(Fe,Cr), Zr(Fe,Cr)2; solidification sequence proposed to explain formation morphology these phases. Alloy phase stability thermal aging at 780°C periods up 30 days. changes that occur during an increase Zr3(Fe,Ni) decrease Zr2(Fe,Ni) content; reaction mechanisms have changes. lattice parameters determined diffraction found be agreement with those previously reported similar This study microstructures first step towards understanding actinide fission product distribution predicting corrosion behavior